Rate theory model of irradiation effects in UO2: Influence of electronic energy losses

IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2024-11-02 DOI:10.1016/j.jnucmat.2024.155493
A. Georgesco , J.-P. Crocombette , G. Gutierrez , C. Onofri , M. Khafizov
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Abstract

To investigate the effect of electronic energy losses on nuclear damage in UO2, we use a simple Rate Theory (RT) model, based on the time evolution of single point defects, governed by their absorption at the surface of TEM lamellae, and by interstitial-type dislocation loops nucleation, solely characterized by their number and average size. We first parametrize the model by fitting six different experimental datasets at various temperatures, ion type and energy (0.39 MeV Xe and 4 MeV Au ion irradiations at 93, 298 and 873 K) where defect evolution in UO2 is dominated by displacement damage caused by nuclear energy losses. The model suggests that dislocation evolution kinetics is driven by monomers diffusion at 873 K. At lower temperature (93 and 298 K) monomer diffusion has little impact and the evolution is governed by the nucleation of loops within the collision cascade. Analysis of four additional experimental datasets at 93 and 298 K where electronic energy losses are strong (single 6 MeV Si and dual simultaneous Xe & Si ion irradiations) required modification of monomer's diffusion coefficients. In the case of single Si ion irradiation, evolution is temperature independent and the enhanced diffusion due to electronic excitations and ionizations are best captured by adding athermal component to the monomer diffusion coefficients. In case of the dual Xe & Si ions irradiation, electronic excitation caused by Si ions impacts the defects pre-generated by Xe ions and enhances defect diffusion by at local heating induced by the thermal spike of Si ions. This effect is best captured by artificially raising the irradiation temperature.
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二氧化铀中辐照效应的速率理论模型:电子能量损失的影响
为了研究电子能量损失对二氧化铀核损伤的影响,我们使用了一个简单的速率理论(RT)模型,该模型基于单点缺陷的时间演化,由其在TEM薄片表面的吸收和间隙型位错环核(仅以其数量和平均尺寸为特征)决定。我们首先通过拟合不同温度、离子类型和能量(93、298 和 873 K 下的 0.39 MeV Xe 和 4 MeV Au 离子辐照)下的六个不同实验数据集,对模型进行了参数化。在较低温度下(93 和 298 K),单体扩散的影响很小,缺陷演化受碰撞级联内的环状成核的支配。在 93 和 298 K 温度下,电子能量损失较大(单次 6 MeV Si 和双次同时 Xe & ;Si 离子辐照),对另外四个实验数据集的分析需要修改单体扩散系数。在单硅离子辐照的情况下,演化与温度无关,电子激发和电离导致的扩散增强可通过在单体扩散系数中加入热分量得到最好的捕捉。在氙和amp; 硅离子双重辐照的情况下,硅离子引起的电子激发会影响氙离子预先产生的缺陷,并通过硅离子热尖峰引起的局部加热来增强缺陷扩散。人为地提高辐照温度最能体现这种效果。
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来源期刊
Journal of Nuclear Materials
Journal of Nuclear Materials 工程技术-材料科学:综合
CiteScore
5.70
自引率
25.80%
发文量
601
审稿时长
63 days
期刊介绍: The Journal of Nuclear Materials publishes high quality papers in materials research for nuclear applications, primarily fission reactors, fusion reactors, and similar environments including radiation areas of charged particle accelerators. Both original research and critical review papers covering experimental, theoretical, and computational aspects of either fundamental or applied nature are welcome. The breadth of the field is such that a wide range of processes and properties in the field of materials science and engineering is of interest to the readership, spanning atom-scale processes, microstructures, thermodynamics, mechanical properties, physical properties, and corrosion, for example. Topics covered by JNM Fission reactor materials, including fuels, cladding, core structures, pressure vessels, coolant interactions with materials, moderator and control components, fission product behavior. Materials aspects of the entire fuel cycle. Materials aspects of the actinides and their compounds. Performance of nuclear waste materials; materials aspects of the immobilization of wastes. Fusion reactor materials, including first walls, blankets, insulators and magnets. Neutron and charged particle radiation effects in materials, including defects, transmutations, microstructures, phase changes and macroscopic properties. Interaction of plasmas, ion beams, electron beams and electromagnetic radiation with materials relevant to nuclear systems.
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